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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20217F9551999-10-14014 October 1999 Application for Amends to Licenses DPR-77 & DPR-79,proposing Change to TS SRs & Bases to Incorporate ARC for Axial Primary Water Stress Corrosion Cracking at Dented Tube Support Plant Intersections ML20217E4211999-10-12012 October 1999 TS Change 99-15 to Licenses DPR-77 & DPR-79,providing Unisolation of Containment Penetrations Under Administrative Controls ML20211K1521999-08-30030 August 1999 TS Change 99-10 to Licenses DPR-77 & DPR-79,providing Clarification to Current TS Requirements for Containment Isolation Valves ML20211M7261999-08-30030 August 1999 TS Change 99-08,for Amends to Licenses DPR-77 & DPR-79 to Provide Alternative to Requirement of Actually Measuring Response times.Marked-up & Revised TS Pages,Encl ML20209B7661999-06-30030 June 1999 Application for Amends to Licenses DPR-77 & DPR-79,updating Current TS Requirements for RCS Leakage Detection & RCS Operational Leakage Specifications to Be Consistent with NUREG-1431 ML20196G4441999-06-24024 June 1999 Application for Amends to Licenses DPR-77 & DPR-79,to Revise TS to Be Consistent with Rev to ISTS Presently Submitted to NEI TSTF for Submittal as Rev to NUREG-1431 ML20196F2121999-06-24024 June 1999 Application for Amends to Licenses DPR-77 & DPR-79,to Change TS Allowing Use of Fully Qualified & Tested Spare Inverter in Place of Any of Eight Required Inverters ML20195E9661999-06-0707 June 1999 Application for Amend to License DPR-79,increasing Max Allowed Specific Activity of Primary Coolant from 0.35 Microcuries/Gram Dose Equivalent I-131 to 1.0 Microcuries/ Gram Dose Equivalent I-131 for Plant Cycle 10 (U2C10) Core ML20206E1551999-04-29029 April 1999 Application for Amends to Licenses DPR-77 & DPR-79, Consisting of TS Change 99-04, Auxiliary Feedwater Suction Pressure Low Surveillance Frequency Rev. Change Deletes Surveillance ML20206E1341999-04-29029 April 1999 Application for Amends to Licenses DPR-77 & DPR-79, Consisting of TS Change Request 99-03, Main Control Room Emergency Ventilation Sys Verses Radiation Monitors. Change Adds LCOs 3.3.3.1 & 3.7.7 & NUREG-1431 Changes ML20204H3991999-03-19019 March 1999 TS Change 99-01 to Licenses DPR-77 & DPR-79,relocating TS Associated with Electrical Equipment Protective Devices to Technical Requirements Manual ML20207D5941999-02-26026 February 1999 Application for Amend to Licenses DPR-77 & DPR-79,relocating TS 3.7.6, Flood Protection Plan & Associated Bases from TS to Plant TRM ML20207D6251999-02-26026 February 1999 Application for Amends to Licenses DPR-77 & DPR-79,revising TS to Provide for Consistency When Exiting Action Statements Associated with EDG Sets ML20199K5841999-01-15015 January 1999 Application for Amends to Licenses DPR-77 & DPR-79,adding New Action Statement to TS 3.1.3.2 That Would Eliminate Need to Enter TS 3.0.3 Whenever Two or More Individual RPIs Per Bank May Be Inoperable,While Maintaining Protection ML20206S0061999-01-15015 January 1999 TS Change 98-09 for Licenses DPR-77 & DPR-79,relocating TS 3.3.3.3, Seismic Instrumentation & Associated Bases from TS to Plant Technical Requirements Manual ML20195H6041998-11-16016 November 1998 Application for Amends to Licenses DPR-77 & DPR-79,revising EDG SRs by Adding Note to Allow SR to Be Performed in Modes 1,2,3 or 4 If Associated Components Are Already OOS for Testing or Maint & Removing SR Verifying Lockout Features ML20154H7201998-10-0808 October 1998 Supplemental Application for Amends to Licenses DPR-77 & DPR-79,changing TS to Add CRMP to Administrative Controls Section & Bases of TS ML20238F1051998-08-27027 August 1998 Application for Amend to License DPR-79,revising TS to Provide for Insertion of Limited Number of Lead Test Assemblies,Beginning W/Unit 2 Operating Cycle 10 Core ML20238F2981998-08-27027 August 1998 Revised Applications for Amends to Licenses DPR-77 & DPR-79, Replacing 72 H AOT of TS 3.8.1.1,Action b,w/7 Day AOT Requirement for Inoperability of One EDG or One Train of Edg.Response to RAI Included in Encl ML20249C6321998-06-26026 June 1998 Application for Amends to Licenses DPR-77 & DPR-79,lowering Specific Activity of Primary Coolant from 1.0 Uci/G Dose Equivalent I-131 to 0.35 Uci/G Dose Equivalent I-131,as Provided in GL 95-05 ML20248E9841998-05-28028 May 1998 Suppl TS Change 95-19 to Licenses DPR-77 & DPR-79,replacing Direct Ref to Nuclear QA Plan in TS Section 6.3.1,facility Staff Qualification,W/Actual Requirements Stated in TVA-NQA-PLN89-A ML20217N3411998-04-30030 April 1998 Application for Amends to Licenses DPR-77 & DPR-79,modifying TS Surveillance Requirement 4.4.3.2.1.b to Change Mode Requirement to Allow PORV Stroke Testing in Modes 3,4 & 5 W/Steam Bubble in Pressurizer Rather than Only in Mode 4 ML20203J1511998-02-25025 February 1998 Application for Amends to Licenses DPR-77 & DPR-79 to Change TS for Units 1 & 2,revising EDG Surveillance Requirements ML20202J6601998-02-13013 February 1998 Application for Amends to Licenses DPR-77 & DPR-79, Incorporating MSIV Requirements to Be Consistent W/Std TS (NUREG-1431) ML20202J7101998-02-13013 February 1998 Application for Amends to Licenses DPR-77 & DPR-79,adding New LCO That Addresses Requirements for Main Feedwater Isolation,Regulating & Bypass Valves ML20202J7421998-02-13013 February 1998 TS Change 97-04 to Application for Amends to Licenses DPR-77 & DPR-79,relocating Snubber Requirements from Section 3.7.9 of TS to Plant Technical Requirements Manual ML20198T4211998-01-21021 January 1998 Suppl TS Change 95-19 to Licenses DPR-77 & DPR-79,revising Title for President,Tva Nuclear & Chief Nuclear Officer to Generic Title of Chief Nuclear Officer ML20199K4441997-11-21021 November 1997 Application for Amend to License DPR-55,adding one-time Allowance Through Operating Cycle 9 to Surveillance Requirement 4.4.3.2.1.b to Perform Stroke Testing of PORVs in Mode 5 Rather than Mode 4,as Currently Required ML20211A3091997-09-17017 September 1997 TS Change 97-02 to Licenses DPR-77 & DPR-79,revising Pressure Differential Surveillance Requirements for Containment Spray Pumps ML20137C8271997-03-19019 March 1997 Revised TS Change 96-01 to Licenses DPR-77 & DPR-79,revising Appropriate Specifications,Surveillances & Bases to Allow for Conversion from Westinghouse Fuel to Framatome Cogema Fuel ML20136J0251997-03-13013 March 1997 Application for Amends to Licenses DPR-77 & DPR-79,revising Allowed Enrichment of Fuel in TS Section 5.6.1.2 for New Fuel Pit Storage Racks from 4.5 to 5.0 Weight % U-235 ML20129D2561996-10-18018 October 1996 Application for Amends to Licenses DPR-77 & DPR-79,removing Existing Footnotes That Limit Application of Apc for Plant SG Tubes to Cycle 8 Operation for Both Units ML20129G7111996-09-26026 September 1996 Application for Amends to Licenses DPR-77 & DPR-79,revising Fire Protection License Conditions & Relocation of Fire Protection Tech Spec ML20113G2421996-09-20020 September 1996 Application for Amends to Licenses DPR-77 & DPR-79, Clarifying Work Shift Durations for Overtime Limits ML20117J3341996-08-28028 August 1996 Application for Amends to Licenses DPR-77 & DPR-79, Revising Psv & MSSV Setpoint Tolerance from Plus or Minus 1% to Plus or Minus 3% ML20117D0921996-08-22022 August 1996 Application for Amends to Licenses DPR-77 & 79 Changing Tss of Sqb Units 1 & 2 by Deleting Table 4.8-1, DG Reliability & Revising Sectio 3.8.1 to Allow a Once Per 18 Month 7 Day AOT for EDGs ML20117D3271996-08-21021 August 1996 TS Change 96-06 to Licenses DPR-77 & DPR-79,removing Surveillance Requirement 4.8.1.1.1.b to Verify Ability to Transfer Unit Power Supply from Unit Generator Supported Circuit to Preferred Power Circuit ML20117D2931996-08-21021 August 1996 TS Change 96-03 to Licenses DPR-77 & DPR-79,revising TS 3.7.1.3, Condensate Storage Tank, to Include New Mode of Applicability to Read Mode 4 When SG Relied Upon for Heat Removal ML20112H0361996-06-0707 June 1996 Application for Amends to Licenses DPR-77 & DPR-79,revising Section 6, Administrative Controls, to Be More Closely Aligned W/Requirements of STSs ML20101N6981996-04-0404 April 1996 TS Change 96-01 to Licenses DPR-77 & DPR-79,allowing Use of Nuclear Fuel Provided by Framatome Cogema Fuels (Fcf). Proprietary & Nonproprietary Versions of Fcf TR Supporting TS Change 96-01 Encl.Proprietary Version of TR Withheld ML20096B3671996-01-0404 January 1996 Application for Amends to Licenses DPR-77 & DPR-79,revising TS Change 95-22,extending Radiation Monitoring Instrumentation Surveillance Period Per GL 93-05 ML20095F0271995-12-12012 December 1995 Application for Amend to License DPR-79,consisting of TS Change 95-23 Revising TS SRs & Bases to Incorporate Alternate S/G Tube Plugging Criteria at Tube Support Plate Intersections,Per GL 95-05 ML20095D5731995-12-0808 December 1995 Application for Amends to Licenses DPR-77 & DPR-79, Consisting of TS Change 95-20,extending Containment Spray & RHR Sys Nozzles Testing Period from 5 to 10 Yrs in Accordance W/Gl 93-05 ML20095D5431995-12-0808 December 1995 Application for Amend to Licenses DPR-77 & DPR-79,consisting of TS Change 93-09,revising Setpoints & Time Delays for AFW loss-of-power & 6.9 Kv Shutdown Board loss-of-voltage & degraded-voltage Instrumentation ML20095D5811995-12-0808 December 1995 Application for Amend to Licenses DPR-77 & DPR-79,revising TSs to Implement Recent Rule Change to 10CFR50,App J ML20092E0191995-09-11011 September 1995 Application for Amend to License DPR-79,consisting of TS Change Request 95-13,rev 1 Re Extension of Response Time Surveillance Requirements for Unit Two Cycle 7 ML20092E0351995-09-0808 September 1995 Application for Amends to Licenses DPR-77 & DPR-79,revising Section 3/4.7.8 to Clarify Intent of Vacuum Relief Flow During TS Required Testing of Auxiliary Bldg Gas Treatment Sys ML20092E2741995-09-0707 September 1995 Revised TS Change 95-15 for Amend to License DPR-77,revising TS Surveillance Requirements & Bases to Incorporate Alternate S/G Tube Plugging Criteria at Tube Support Plate Intersections,Per GL 95-05 ML20091K4241995-08-21021 August 1995 Proposed TS Change 95-21 to Licenses DPR-77 & DPR-79, Revising TS LCO 3.7.5.c to Allow for Increase in Ultimate Heat Sink Temp to 87 F Until 950930 ML20087D3751995-08-0707 August 1995 Application for Amends to Licenses DPR-77 & DPR-79,revising Time Constants for Overtemp Delta Temp & Overpower Delta Temp Equations 1999-08-30
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20217F9551999-10-14014 October 1999 Application for Amends to Licenses DPR-77 & DPR-79,proposing Change to TS SRs & Bases to Incorporate ARC for Axial Primary Water Stress Corrosion Cracking at Dented Tube Support Plant Intersections ML20217E4211999-10-12012 October 1999 TS Change 99-15 to Licenses DPR-77 & DPR-79,providing Unisolation of Containment Penetrations Under Administrative Controls ML20212F4601999-09-23023 September 1999 Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively, Approving Request to Revise TSs to Allow Use of Fully Qualified & Tested Spare Inverter in Place of Any of Eight Required Inverters ML20211K1521999-08-30030 August 1999 TS Change 99-10 to Licenses DPR-77 & DPR-79,providing Clarification to Current TS Requirements for Containment Isolation Valves ML20211M7261999-08-30030 August 1999 TS Change 99-08,for Amends to Licenses DPR-77 & DPR-79 to Provide Alternative to Requirement of Actually Measuring Response times.Marked-up & Revised TS Pages,Encl ML20209B7661999-06-30030 June 1999 Application for Amends to Licenses DPR-77 & DPR-79,updating Current TS Requirements for RCS Leakage Detection & RCS Operational Leakage Specifications to Be Consistent with NUREG-1431 ML20196G4441999-06-24024 June 1999 Application for Amends to Licenses DPR-77 & DPR-79,to Revise TS to Be Consistent with Rev to ISTS Presently Submitted to NEI TSTF for Submittal as Rev to NUREG-1431 ML20196F2121999-06-24024 June 1999 Application for Amends to Licenses DPR-77 & DPR-79,to Change TS Allowing Use of Fully Qualified & Tested Spare Inverter in Place of Any of Eight Required Inverters ML20195E9661999-06-0707 June 1999 Application for Amend to License DPR-79,increasing Max Allowed Specific Activity of Primary Coolant from 0.35 Microcuries/Gram Dose Equivalent I-131 to 1.0 Microcuries/ Gram Dose Equivalent I-131 for Plant Cycle 10 (U2C10) Core ML20207A5781999-05-20020 May 1999 Errata to Amend 163 to OL DPR-79 on 931126.SR 4.1.1.1.1.d Was Inadvertently Omitted from Pp 3/4 1-1 of Unit 2 TS ML20206E1341999-04-29029 April 1999 Application for Amends to Licenses DPR-77 & DPR-79, Consisting of TS Change Request 99-03, Main Control Room Emergency Ventilation Sys Verses Radiation Monitors. Change Adds LCOs 3.3.3.1 & 3.7.7 & NUREG-1431 Changes ML20206E1551999-04-29029 April 1999 Application for Amends to Licenses DPR-77 & DPR-79, Consisting of TS Change 99-04, Auxiliary Feedwater Suction Pressure Low Surveillance Frequency Rev. Change Deletes Surveillance ML20204H3991999-03-19019 March 1999 TS Change 99-01 to Licenses DPR-77 & DPR-79,relocating TS Associated with Electrical Equipment Protective Devices to Technical Requirements Manual ML20207D5941999-02-26026 February 1999 Application for Amend to Licenses DPR-77 & DPR-79,relocating TS 3.7.6, Flood Protection Plan & Associated Bases from TS to Plant TRM ML20207D6251999-02-26026 February 1999 Application for Amends to Licenses DPR-77 & DPR-79,revising TS to Provide for Consistency When Exiting Action Statements Associated with EDG Sets ML20206S0061999-01-15015 January 1999 TS Change 98-09 for Licenses DPR-77 & DPR-79,relocating TS 3.3.3.3, Seismic Instrumentation & Associated Bases from TS to Plant Technical Requirements Manual ML20199K5841999-01-15015 January 1999 Application for Amends to Licenses DPR-77 & DPR-79,adding New Action Statement to TS 3.1.3.2 That Would Eliminate Need to Enter TS 3.0.3 Whenever Two or More Individual RPIs Per Bank May Be Inoperable,While Maintaining Protection ML20195H6041998-11-16016 November 1998 Application for Amends to Licenses DPR-77 & DPR-79,revising EDG SRs by Adding Note to Allow SR to Be Performed in Modes 1,2,3 or 4 If Associated Components Are Already OOS for Testing or Maint & Removing SR Verifying Lockout Features ML20154H7201998-10-0808 October 1998 Supplemental Application for Amends to Licenses DPR-77 & DPR-79,changing TS to Add CRMP to Administrative Controls Section & Bases of TS ML20238F1051998-08-27027 August 1998 Application for Amend to License DPR-79,revising TS to Provide for Insertion of Limited Number of Lead Test Assemblies,Beginning W/Unit 2 Operating Cycle 10 Core ML20238F2981998-08-27027 August 1998 Revised Applications for Amends to Licenses DPR-77 & DPR-79, Replacing 72 H AOT of TS 3.8.1.1,Action b,w/7 Day AOT Requirement for Inoperability of One EDG or One Train of Edg.Response to RAI Included in Encl ML20249C6321998-06-26026 June 1998 Application for Amends to Licenses DPR-77 & DPR-79,lowering Specific Activity of Primary Coolant from 1.0 Uci/G Dose Equivalent I-131 to 0.35 Uci/G Dose Equivalent I-131,as Provided in GL 95-05 ML20248E9841998-05-28028 May 1998 Suppl TS Change 95-19 to Licenses DPR-77 & DPR-79,replacing Direct Ref to Nuclear QA Plan in TS Section 6.3.1,facility Staff Qualification,W/Actual Requirements Stated in TVA-NQA-PLN89-A ML20217N3411998-04-30030 April 1998 Application for Amends to Licenses DPR-77 & DPR-79,modifying TS Surveillance Requirement 4.4.3.2.1.b to Change Mode Requirement to Allow PORV Stroke Testing in Modes 3,4 & 5 W/Steam Bubble in Pressurizer Rather than Only in Mode 4 ML20203J1511998-02-25025 February 1998 Application for Amends to Licenses DPR-77 & DPR-79 to Change TS for Units 1 & 2,revising EDG Surveillance Requirements ML20202J6601998-02-13013 February 1998 Application for Amends to Licenses DPR-77 & DPR-79, Incorporating MSIV Requirements to Be Consistent W/Std TS (NUREG-1431) ML20202J7421998-02-13013 February 1998 TS Change 97-04 to Application for Amends to Licenses DPR-77 & DPR-79,relocating Snubber Requirements from Section 3.7.9 of TS to Plant Technical Requirements Manual ML20202J7101998-02-13013 February 1998 Application for Amends to Licenses DPR-77 & DPR-79,adding New LCO That Addresses Requirements for Main Feedwater Isolation,Regulating & Bypass Valves ML20198T4211998-01-21021 January 1998 Suppl TS Change 95-19 to Licenses DPR-77 & DPR-79,revising Title for President,Tva Nuclear & Chief Nuclear Officer to Generic Title of Chief Nuclear Officer ML20199K4441997-11-21021 November 1997 Application for Amend to License DPR-55,adding one-time Allowance Through Operating Cycle 9 to Surveillance Requirement 4.4.3.2.1.b to Perform Stroke Testing of PORVs in Mode 5 Rather than Mode 4,as Currently Required ML20211A3091997-09-17017 September 1997 TS Change 97-02 to Licenses DPR-77 & DPR-79,revising Pressure Differential Surveillance Requirements for Containment Spray Pumps ML20137C8271997-03-19019 March 1997 Revised TS Change 96-01 to Licenses DPR-77 & DPR-79,revising Appropriate Specifications,Surveillances & Bases to Allow for Conversion from Westinghouse Fuel to Framatome Cogema Fuel ML20136J0251997-03-13013 March 1997 Application for Amends to Licenses DPR-77 & DPR-79,revising Allowed Enrichment of Fuel in TS Section 5.6.1.2 for New Fuel Pit Storage Racks from 4.5 to 5.0 Weight % U-235 IA-97-261, Amend 220 to License DPR-77,authorizing Operation at Reactor Core Power Levels Not in Excess of 3,411 Megawatts Thermal1997-03-0404 March 1997 Amend 220 to License DPR-77,authorizing Operation at Reactor Core Power Levels Not in Excess of 3,411 Megawatts Thermal ML20211K5631997-03-0404 March 1997 Amend 220 to License DPR-77,authorizing Operation at Reactor Core Power Levels Not in Excess of 3,411 Megawatts Thermal ML20129D2561996-10-18018 October 1996 Application for Amends to Licenses DPR-77 & DPR-79,removing Existing Footnotes That Limit Application of Apc for Plant SG Tubes to Cycle 8 Operation for Both Units ML20129G7111996-09-26026 September 1996 Application for Amends to Licenses DPR-77 & DPR-79,revising Fire Protection License Conditions & Relocation of Fire Protection Tech Spec ML20113G2421996-09-20020 September 1996 Application for Amends to Licenses DPR-77 & DPR-79, Clarifying Work Shift Durations for Overtime Limits ML20117J3341996-08-28028 August 1996 Application for Amends to Licenses DPR-77 & DPR-79, Revising Psv & MSSV Setpoint Tolerance from Plus or Minus 1% to Plus or Minus 3% ML20117D0921996-08-22022 August 1996 Application for Amends to Licenses DPR-77 & 79 Changing Tss of Sqb Units 1 & 2 by Deleting Table 4.8-1, DG Reliability & Revising Sectio 3.8.1 to Allow a Once Per 18 Month 7 Day AOT for EDGs ML20117D2931996-08-21021 August 1996 TS Change 96-03 to Licenses DPR-77 & DPR-79,revising TS 3.7.1.3, Condensate Storage Tank, to Include New Mode of Applicability to Read Mode 4 When SG Relied Upon for Heat Removal ML20117D3271996-08-21021 August 1996 TS Change 96-06 to Licenses DPR-77 & DPR-79,removing Surveillance Requirement 4.8.1.1.1.b to Verify Ability to Transfer Unit Power Supply from Unit Generator Supported Circuit to Preferred Power Circuit ML20112H0361996-06-0707 June 1996 Application for Amends to Licenses DPR-77 & DPR-79,revising Section 6, Administrative Controls, to Be More Closely Aligned W/Requirements of STSs ML20101N6981996-04-0404 April 1996 TS Change 96-01 to Licenses DPR-77 & DPR-79,allowing Use of Nuclear Fuel Provided by Framatome Cogema Fuels (Fcf). Proprietary & Nonproprietary Versions of Fcf TR Supporting TS Change 96-01 Encl.Proprietary Version of TR Withheld ML20096B3671996-01-0404 January 1996 Application for Amends to Licenses DPR-77 & DPR-79,revising TS Change 95-22,extending Radiation Monitoring Instrumentation Surveillance Period Per GL 93-05 ML20095F0271995-12-12012 December 1995 Application for Amend to License DPR-79,consisting of TS Change 95-23 Revising TS SRs & Bases to Incorporate Alternate S/G Tube Plugging Criteria at Tube Support Plate Intersections,Per GL 95-05 ML20095D5431995-12-0808 December 1995 Application for Amend to Licenses DPR-77 & DPR-79,consisting of TS Change 93-09,revising Setpoints & Time Delays for AFW loss-of-power & 6.9 Kv Shutdown Board loss-of-voltage & degraded-voltage Instrumentation ML20095D5731995-12-0808 December 1995 Application for Amends to Licenses DPR-77 & DPR-79, Consisting of TS Change 95-20,extending Containment Spray & RHR Sys Nozzles Testing Period from 5 to 10 Yrs in Accordance W/Gl 93-05 ML20095D5811995-12-0808 December 1995 Application for Amend to Licenses DPR-77 & DPR-79,revising TSs to Implement Recent Rule Change to 10CFR50,App J ML20092E0191995-09-11011 September 1995 Application for Amend to License DPR-79,consisting of TS Change Request 95-13,rev 1 Re Extension of Response Time Surveillance Requirements for Unit Two Cycle 7 1999-09-23
[Table view] |
Text
TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 374ot 400 Chestnut Street Tower II May 25, 1982 Director of Nuclear Reactor Regulation ,
Attention: Ms. E. Adensam, Chief Licensing Branch No. 4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Ms. Adensam:
In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 In accordance with 10 CFR Part 50.90, enclosed are 40 copies of proposed revisions to the Sequoyah Nuclear Plant Operating Licenses DPR-77 (Enclosure 1) and DPR-79 (Enclosure 2). The proposed license amendments request changes in the operating license conditions regarding environmental qualification of safety-related electrical equipment (NUREG-0588) and controi room design review for each unit. Each enclosure identifies the existing conditions, the proposed changes, and the basis for each change.
Enclosure 1 provides the requested changes in the unit 1 operating license, DPR-77; and Enclosure 2 provides the requested changes in the unit 2 operating license, DPR-79.
In accordance with the provisions of 10 CFR Part 170, we have determined the changes to be Class II for unit 1 and Class I for unit 2. These classifications are based on the facts that the amendment is adminis-trative in nature and that the changes apply to two identical units on the same site. The remittance fee of $1,600 is being wired to the Nuclear Regulatory Commission, Attention: Licensing Fee Management Branch.
Very truly yours, TENNESSEE VALLEY AUTHORITY os M D. S. Kammer Sworn to and subscribed before me Nuclear Engineer Dh[
this M day of (2 vV' 1982 f
[ G!4 Lush a K! . I (
Notary /Public //
My Commission Expires
/ /
f f'd Enclosure (40) cc: See page 2 8206030121 820525 PDR ADOCK 05000327 PDR An Equal Opportunity Employer p
Director of Nuclear Reactor Regulation May 25, 1982 cc: U.S. Nuclear Regulatory Commission Region II Attn: Mr. James P. O'Reilly, Regional Administrator 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303
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ENCLOSURE 1
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PROPOSED CHANGES '11) 711E SEQUOYAH NUCLEAR PLANT UNIT 1 )
OPERATING LICENSE
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ltem (1) - Environmental Qualification of Safety-Related Electrical Eautoment E11stine Conditions 2.C(12).a No later than November 1,1980, TVA shall submit information to show compliance with the requirements of NUREG-0588, 'Interin Staff Fosition on Environmental Qualification of Safety-Related Electrical Equipment,' for safety related equipment exposed to a harsh snvironment. Implementation shall be in accordance with NUREG-0588 by June 30, .1982.
2.C(12).b By no later than December 1,1980, complete and auditable records must be available and maintained at a central location which describe the environmental qualification method used for all safety related electrical equipment in suf ficient detail to document the degree of compliance with the DOR Guidelines or NUREG-0583. Thereafter, such records should be updated and maintained current a s equipment is replaced, further tested, or otherwise further qualified to document complete compliance by June 30,1982.
2.C(12).c By no later than June 30, 1982, all safety-related electrical equipment in the facility shall be qualified in accordance with the provisions of: Division of Operating Reactors ' Guidelines for Evaluating Environmental Qualification of Class IE Electrical Equipment in Operating Reactors' (DOR Guidelines); or NUREG-05 88, ' Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment,' December 1979. Copies of these documents are attached to the Order for Modificaton of License DPR-77 dated November 6,1980.
Pronosed Channes 2.C(12).a No later than November 1,1980, TVA shall submit information to show compliance with the requirements of NUREG-0588, ' Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment ,' for safety-related equipment exposed to a harsh environment. Implementation shall be in accordance with NUREG-0588 by the end of the second refueling outage after March 31,1982 but not later than November 30, 1985.
2.C(12).b By no later than December 1,1980, complete and auditable records must be available and maintained at a central location which describe the environmental qualification method used for all safety-related electrical equipment in sufficient detail to document the degree of compliance with the DOR Guidelines or NUREG-05 88. Thereafter, such records should be updated and
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Page 2 i l
- i 1 maintained current as equipment is replaced, further tested, or otherwise further qualified to document complete compliance by 1 the end of the second refueling outage after March 31,1982 but )
no later than November 30, 1985. l l 2.C(12).c All safety-related electrical equipment in the facility shall be qualified in accordance with the provisions of: Division of '
Operating Reactors ' Guidelines for Evaluating Environmental Qualification of Class IE Electrical Equipment in Operating l Reactors * (DOR Guidelines): or NUREG-0588, ' Interim Staff Position on Environmental Qualification of Safety-Related i
Electrical Equipment,' December 1979, or the requirements of proposed regulation, 10 CFR 50.49, ' Environmental Qualification of Electrical Equipment for Nuclear Power Plants,' by the end of the second refueling outage after March 31, 1982 but no later than November 30, 1985.
Justification In previous submittals to the NRC to comply with the requirements of NUREG-0588 and with the requirements of 2.C(10).c of the unit 2 operating license for the Sequoyah Nuclear Plant, we have indicated that we would make overy reasonable effort to comply with the requirements of NUREG-0588.
In the July 7-10, 1981 neeting with NRC on equipment qualification, we indicated concerns with our ability to comply with the deadline and provided examples and reasons. A sammary of examples is provided in Attachment 1. These examples are typical of the inability to obtain qualified components by the current deadline.
We, therefore, recommend that the deadline be in accordance with the replacement schedule established by each utility that is reviewed and l approved by the NRC but consistent with the implementation schedule provided in the proposed addition (50.49) to the Code of Federal Regulations. The schedule proposed by the new regulation 50.49 has final environmental qualification by the second refueling outage af ter March 31, 1982 but no later than November 30, 1985. We believe that continued operation of our Sea,noyah Nuclear Plant is justified.
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Item (2) - Control Room Deslan Enistin. Condition Prior to start-up af ter first refueling, TVA shall complete the detailed Control Room Design Review. As part of this review, TVA shall consider benefits of installing data recording and logging equipment in the control '
room to correct the deficiencies associated with the trending of important parameters on strip chart recorders used in the control room.
Pronomad Conditio.A TVA shall complete the detailed control room design review in accordance with the schedule to be spscified for operating reactors in NUREG-0700. As part of this review, TVA shall consider benefits of installing data recording and logging equipment in the control room to correct the deficiencies associated with the trending of important parameters on strip chart recorders used in the control room.
Justifloation As stated in the Sequoyah SER, Supplements 2 and 5, we have taken correct i actions to improve the operator effectiveness during an upset or accident condition. The NRC concluded that Sequoyah could be safely operated with these improvements. However, we were required to complete the detailed control room review on the same schedule as other licensees with operating plants. Even though NUREG-0700 was officially issued during the f all of 1981, no implementation schedule has yet been defined.
i At the time the existing license condition was issued on unit 1 of our Sequoyah Nuclear Plant, this date was thought to be consistent with the expsoted implementation schedule for the detailed control room review, that would be included in NUREG-0700. Since this schedule has changed significantly, and in order to be consistent with our understanding of the intent to the requirement as stated in the Sequoyah SERs, we propose changing the license condition to coincide with the schedule to be imposed
- on other licensees of operating reactors. We believe that continued operation of the plant is justified.
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ATTAGMENT 1 TO ENCLOSURE 1 Examples of Equipment Not Capable of Meeting the June 30, 1982 Deadline
- 1. Pressure transmitters (PT) and differential pressure transmitters (DPT), 10-50MA range: Barton appears to be on the only source for qualified instruments capable of meeting TVA's requirements.
Qualification is expected in October 1981 and procurement lead time would result in delivery in later 1982. This date could be severely delsyed if other utilities tax Barton's production capabilities.
- 2. Pressure switches, dif ferential pressure switches and flow switches:
The ASCO models may have to be totally rotested to meet qualification req 3irements. Completion of qualification testing is not expected until February 1983. Comparable Barton instruments lack adequate
, seismic qualification and would require modification or further testing. Additionally, suppliers will not test to TVA's specific (extreme) environmental conditions. Procurement delivery dates cannot be expected until 1984.
- 3. Level switches, fl ow type: Magnetrol appears to be the only source for qualified instruients: howev e r, the qualification testing is not expected until 1983 and delivery in 1984.
- 4. 4160/480-V transformers: Procurement of qualified replacement components will require significant lead time sud delivery is expected in late 1983.
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ENCLOSURE 2 ;i PROPOSED CHANGES TO 'IEE SBQUOYAH NUCLEAR PLANT UNIT 2 OPERATING LICENSE Item (1) - Environmental Qualification of Safetv-Related Eauinment.
NUREG-0588 Existina Conditions 2.C(10).a No later than June 30, 1982,' 'IVA shall be in compliance with the requirements of NUREG-0588, ' Interim Staff Position on Environmental Qualification of safety-Related Electrical Equipment,' for safety related equipment exposed to a harsh environment .
2.C(10).b Complete and auditable records must be available and maintained -
at a central location which describe the environmental qualification method used for all safety-related electrical equipment in sufficient detail to document the degree of compliance with the DOR Guideline s or NUREG-0588. Such records should be updated and maintained current as equipment is i replaced, further tested, or otherwise further qualified to document complete compliance by June 30, 1982.
2.C(10).c Within 90 days of receipt of the equipment qualification safety evaluation, the licensee shall either (1) provide missing documentation -identified in Sections 3 and 4 of the equipment qualification safety evaluation which will demonstrate compliance of the applicable equipment with NUREG-0588, or (ii) commit to corrective actions which will result in documentation of compliance of applicable equipment with NUREG-0588 no later than June 30, 1982.
Pronomad Conditions 4 ,
2.C(10).a 'IVA shall be in compliance with the requirements of NUREG-0588,
' Interim Staff Position on Environmental Qualification of Saf ety-Related Electrical Equipment, ' for safety-related equipment exposed to a harsh environment, or the requirements of the proposed regulation, 10 CFR 50.49, ' Environm ent al Qualification of Electrical Equipment for Nuclear Power Plants,'
by the end of the second refueling outage af ter March 31, 1982 but no later than November 30, 1985.
2.C(10).b Complete and auditable records must be available and maintained at a central location which describe the environmental qualification method used for all safety-related electrical ,
equipment in sufficient detail to document the degree of compliance with the DOR Guideline s or NUREG-0588 Such records
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should be updated and maintained current a s equipment is replaced, further tested, or otherwise further qualified to l docum ent complete compliance by the date required by the proposed regulation 50.49, ' Environmental Qualification of Electrical Equipsent for Nuclear Power Plants.'
2.C(10) c Mithin 90 days of receipt of the equipment qualification safety evaluation, the licensee shall either (i) provide missing documentation identified in Sections 3 ar.d 4 of the equipment qualification safety evaluation which will demonstrate compliance of the applicable equipment with NUREG-0588, or (ii) commit to corrective actions which will result in documentation of compliance of applicable equipment with NUREG-0588 by the date required the proposed regulation 50.49, ' Environmental Qualification of Electrical Equipment for Nuclear Power Plants.'
Justification Same as for unit 1.
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,Page 3 Item (2) - Control Room Dealan Review Enlatina Condition Prior to startup af ter first refueling of unit 1 or unit 2, whichever osents first, TVA shall complete the detailed Control Room Design Review.
As part of this review, TVA shall consider benefits of installing data recording and logging equipment in the control room to correct the deficiencies associated with the trending of important parameters on strip ,
chart recorders used in the control room.
Pronosed Condition TVA shall complete the detailed control room design review in accordance with the schedule to be specified for operating reactors in NUREG-0700. As part of this review, TVA shall consider benefits of installing data recording and logging equipment in the control room to correct the deficiencies assoaisted with the trending of Important parameters on strip chart recorders used in the control room.
J us t if lo at ion Same as for unit 1.
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